ML20203L652
| ML20203L652 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/22/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| 86-497, NUDOCS 8608290032 | |
| Download: ML20203L652 (17) | |
Text
i V1HOINIA EI.ECTRIC AND Powcu COMPANY Riclixoxu,VINGINIA u3uG1 August 22, 1986~
Vaca Passionny Nurs. mas Ormsesysome Mr. Harold R. Denton, Director Serial No.86-497 Office of Nuclear Reactor Regulation E&C/NBR: hts:7887N Attn: Mr. Lester S. Rubenstein, Director Docket Nos. 50-338 PWR Project Directorate No. 2 50-339 Division of PWR Licensing-A License Nos. NPF-4 U. S. Nuclear Regulatory Camtission NPF-7 Washington, D.C.
20555 Gentlanen:
VIRGINIA ELECTRIC AND POWER COMPANY
_NORni ANNA POWER STATION UNIT NOS.1 AND 2 AMENDMENT 'IO OPERATING LICENSES NPF-4 AND NPF-7 Pursuant to 10CFR50.90, Virginia Electric and Power Ccmpany regaests an amendment, in the form of changes to Operating License Nos. NPF-4 and NPF-7 for North Anna Power Station Unit Nos. 1 and 2.
'Ihe proposed changes will extend the duration of both full power Operating Licenses to 40 years frcm the date of issuance of the Operating Licenses. A license term e" 40 years is permitted by 10CFR50.51 and is consistent with the original design considerations.
Approval of the proposed amendments would also be consistent with recent NBC actions.
North Anna Power station is currently licensed for a period of 40 years ccomencing with the issuance of the construction permit, which was issued for both units on February 19, 1971. The current licenses will therefore expire at midnight on February 18, 2011 and Febrt.ary 19, 2011 for Units 1 and 2 respectively. This request would allow for 40 full years of operation by changing the license expiration dates to April 1, 2018 for Unit 1 (NPF-4) and to August 21, 2020 for Unit 2 (NPF-7). Attachmer.t 1 provides the proposed changes to the Facility Operating Licenses for North Anna Units 1 and 2.
A Safety Evaluation and Envirorrnental Assessment is provided in Attachment 2.
'Ihis regaest has been reviewed and approved by the Station Nuclear Safety and Operating Ccxtmittee and the Safety Evaluation and Control staff. It has been determined that this request does not involve an unreviewed safety question as defined in 10CFR50.59 or.a significant hazards consideration as defined in 10CFR50.92.
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p\\ bhUQ 0(h 8608290032 G60822 PDR ADOCK 05000338
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V We'have evaluated this request in accordance with the criteria in 10CFR170.12.
A voucher check in the amount of $150 is enclosed as an application fee.
l Very truly yours, n
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\\M W. L. Stewart 4
l Attachments (1)
Proposed Operating License changes (2)
Safety Evaluation and Environmental Assessment (3) Voucher check for $150
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cc: Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. Albert F. Gibson, Acting Director Division of Reactor Projects NRC Region II 1
Mr. Ieon B. Engle NRC North Anna Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A 1
Mr. J. L. Caldwell I
NBC Senior Resident Inspector North Anna Power Station 3
Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 1
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COMMONWEALTH OF VIRGINIA )
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The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W.
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Stewart who is Vice President -
Nuclear Operations, of Virginiu Electric and Power Company.
He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this
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1 Ftwixd Ganges to Operating Licenses
ATDCHMENE 1 NORPH ANNA UNITS 1 AND 2 OPERATING LICENSE CHANGES 40 YEAR OPERATING LICENSE l
I Unit 1: Revise licence condition 2.H to read, "'Ihis license is effective as of the date of issuance, and shall expire at midnight April 1, 2018."
Unit 2: Revise license condition 2.I to read, "This license is effective as of the date of issuance, and shall expire at midnight August 21, 2020."
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1 Attadunant 2 Safety Evaluation and Envitua-sital Assessnent 1
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SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT FOR A 40 YEAR OPERATING LICENSE NORTH ANNA POWER STATION, UNITS 1 AND 2 61-WBR-96678-1
TABLE OF CONTENTS Section Title Page I.
Introduction 3
II.
Safety Evaluation 4
III.
Environmental Assessment 5
IV.
ALARA Review 6
V.
Economic Evaluation 7
VI.
Unreviewed Safety Question Evaluation 8
VII.
Significant Hazards Consideration 9
Evaluation VIII.
Conclusions 10
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61-WBR-9667B-2
1 I.
INTRODUCTION The current operating licenses for North Anna Units 1 and 2 expire 40 years from the date of issuance of the construction permit. Because of the time required for construction, fuel loading and startup testing, the effective periods of Operating Licenses NPF-4 (North Anna Unit 1) and NPF-7 (North Anna Unit 2) are approximately 33 years and 301 years respectively.
Current NRC policy is to issue operating licenses fcr a 40 year period beginning with the date of issuance, consistent with the guidelines of 10CFR50.51 and Section 103.C of the Atomic Energy Act of 1954(42USC2133.C),asamended.
This report has been prepared to support the extension of the North Anna Unit 1 and 2 operating licenses approximately 7 and 91 years respectively, to provide for 40 years of operation. The requested expiration dates for the operating licenses are as follows:
Issuance of Requested OL Unit Full Power OL Expiration Date 1
April 1, 1978 April 1, 2018 2
August 21, 1980 August 21, 2020 This report summarizes the safety, environmental, ALARA and economic reviews that have been performed to demonstrate that this request to amend the operating licenses does not involve an unreviewed safety question or a significant hazards consideration.
e 61-WBR-96678-3
I II.
SAFETY EVALUATION The request for the extension of the operating licenses is based on the fact that a 40 year operating life (Reference UFSAR Table 5.1-1) was considered by the NSSS Vendor (Westinghouse Electric Corporation) and Architect Engineer (Stone and Webster Engineering Corporation) during the design and construction of the plant. A 40 year design life, however, does not preclude that some equipment may require repair and/or replacement during the lifetime of the station.
Design features have been incorporated which provide for the inspectability of structures, systems and equipment.
The surveillance, inscection, testing and maintenance practices which have been impleme.nted in accordance with applicable codes, standards and the facility Technical Specifications, provide assurance that degradation in plant equipment-will be identified and corrected.
In accordance with 10CFR50.49, " Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants", aging analyses have been performed for safety-related electrical equipment identifying qualified lifetimes for this equipment.
These lifetimes are incorporated into plant equipment maintenance and replacement practices to ensure that safety-related electrical equipment remains qualified and available to perform its safety function regardless of the overall age of the plant.
Reactor vessel material analyses have shown that the expected cumulative neutron fluence on the reactor vessel will not be a limiting consideration for a 40 year operating life.
Periodic analysis of the surveillance specimens inside the reactor also allows for monitoring the actual cumulative effects of neutron fluence.
Periodic vessel inservice inspection and testing requirements provide additional assurance that any degradation will be identified.
On-site storage of spent nuclear fuel will be available through the year 1999.
Additional onsite storage through the use of fuel rod consolidation or dry cask storage, will be added as necessary.
Also, the U.S. Department of Energy should make available off-site storage and disposal, under the Nuclear Maste Policy Act of 1982, befare 2011.
Therefore, storage of spent fuel generated after 2011 is not a concern.
No new safety concerns are introduced by this proposed amendment since
-(1) a 40 year life was considered in the design of the plant and since (2) new or revised accident analyses, plant modifications, procedure changes, UFSAR revisions and Technical Specification revisions are not required.
Nete however, that since the issuance of the operating licenses, numerous modifications have been implemented to enhance safety and to address issues such as Appendix R, Reg. Guide 1.97, ALAP.A (see Section IV), Equip 9ent Qualification, and the TMI-2 Lessons Learned (NUREG 0737).
61-WBR-96678-4
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III.
ENVIRONMENTAL ASSESSMENT The North Anna 182 Final Safety Analysis Report (FSAR) and Environmental Report (for North Anna Power Station, Units 1, 2, 3 and 4) were prepared in support of the original License Application which requested an operating license for units 182 for a term of 40 years.
Therefore 40 years of operation was considered in the preparation of the Environmental Report.
Page 10 of the report specifically states that.the useful life of a nuclear power station of tFe North Anna type is expected to be 30 -
40 years, depending upon when improved generating plants warrant replacement for economic or other reasons. However, the Environmental Report is not always clear with respect to the maximum number of years of operation covered by the evaluations.
For example, normal operational releases are provided in terms of an annual impact and the economic analysis is based on a 30 year useful life, which was a standard assumption for these types of evaluations. The useful life assumed in 4
these economic evaluations, however, has no bearing on the actual number of years a station can be safely operated.
Vepco has determined that the operation of the North Anra Units for an additional 7-9) years would not alter the favorable conclusions reached in the Environmental Report, because the extension of the operating license does not involve any plant modifications or plant procedure changes which could adversely impact the environment. The station's radiological monitoring programs and a study performed since the issuance of. the Environmental Report have further demonstrated that the station is not adversely impacting the environment.
The study demonstrated that the thermal discharges from the station are not adversely affecting aquatic life in Lake Anna and in the lower North Anna River.
This study has be'en submitted to the Virginia State Water Control Board.
Operation of the station is further regulated by a National Pollutant Discharge Elimination System permit.
The pnpulation growth in areas surrounding the station has also been reviewed.
From census data obtained in 1980, it has been concluded that the population within the 10 mile Emergency Planning Zone (EPZ) of the station has been growing at an annual rate of approximately 4%, which is greater than originally predicted in the Environmental Report. This does not impact the conclusions in the Environmental Report since the areas around the station are still primarily rural and are relatively low in population.
61-WBR-96678-5
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IV.
ALARA REVIEW A formal ALARA Program was implemented on January 1,1983. A Corporate ALARA Manual and Station ALARA Manuals were-developed to provide the guidelines and procedures to execute the program.
In addition, the Company approved a Radiation Protection Plan (RPP) in early 1984 which also addresses the ALARA Program. A Transition Plan was developed to serve as a means of effecting the transition from the current radiation protection program to that described in the RPP. The Corporate ALARA Manual and Station ALARA Manuals are being incorporated into procedures implementing the ALARA program specified in the RPP. The procedures will enhance personnel training requirements, direct management participation on the station and corporate ALARA committees, and increase emphasis to the ALARA concept.
The Company also sponsors an awards program for employees submitting exposure saving suggestions.
North Anna's personnel exposure average for the past 5 years has been below the national average.
Important modifications being implemented at North Anna to further reduce personnel exposure include:
permanent reactor head shields, removal of nonessential large bore snubbers, multiple stud tensioner/detensioner for the steam generators' primary manways, and a computerized photo documentation of the plant for ALARA preplanning.
Over 150 ALARA suggestions have been submitted at North Anna since January,1983.
Over 50 of these suggestions have been approved and over 30 have already been implemented.
Based on management's commitment to the ALARA concept, the implementation of exposure saving modifications, and ongoing programs to reduce exposure, the occupational exposure expected to be expended during the period covered by the requested amendment is not a significant consideration.
61-WBR-96678-6
V..
ECON 0 HIC EVALUATION Operation of North Anna Power Station beyond its current operating:
license period will be a considerable benefit to us and to our residential, commercial and industrial customers.
Nuclear generated electricity-is the least expensive power generated and sold by the company. The additional. years of plant operation allowed by the proposed change would defer the need to install replacement base load capacity and defer the need for substantial additional capital expenditures. The continued operation of the station would also be beneficial to the. tax-base and to the economy of the surrounding areas.
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61-WBR-96678-7 l
VI.
UNREVIEWED SAFETY QUESTION EVALUATION The proposed license change to permit a 40 year operating life does not constitute an unreviewed safety question as defined in 10CFR50.59 since:
a.
The proposed amendment will not increase the probability of occurrence or the consequences of an accident or nalfunction of equipment important to safety and pretiously evaluated in the Updated Final Safety Analysis Report since no changes are required to the design or operation of the station.
This amendment does not involve any new or revised accident cnalyses, physical modifications to the plant, plant procedures changes, UFSAR revisions or Technical Specifications revisions.
The proposed license extensions are within the original design considerations for the station and the current surveillance, inspecting, testing and maintenance practices provide assurance that degradation in plant equipment will be identified and corrected throughout the lifetime of the facility.
b.
The proposed amendment will not create a possibility for an accident or malfunction of a different type than any evaluated previously in the Updated Final Safety Analysis Report since no changes are required to the design or operation of the station.
c.
The implementation of this modification will not reduce the margin of safety as defined in the basis of any Technical Specification since the proposed change does not a'ffect the Technical Specifications or any of the accident analyses which form the basis for the Technical Specifications.
61-WBR-96678-8
VII.
SIGNIFICANT HAZARDS CONSIDERATION EVALUATION The proposed revisions to the Facility Operating Licenses for North Anna Power Station do not involve any changes in the design or operation of the station, but only contemplate a change to the expiration dates of the current licenses.
These extensions are within the range permissible by the Commission's regulations, specifically 10CFR50.51.
In addition, a finding of no significant hazards consideration is consistent with recent NRC actions on applications of this type (Reference Baltimore Gas and Electric, Calvert Cliffs).
.As discussed in detail in this report, the proposed extension will have no significant impact on the safe operation of the plant or present an undue risk to the health and safety of the public.
The proposed license amendment to permit a 40 year operating life does not constitute a significant hazards consideration as defined in 10CFR50.92 since:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of any accident previously evaluated since no changes are required to the design or operation of the station. This amendment does not involve new or revised safety analyses, physical plant modifications, procedure changes, UFSAR revisions or Technical Specification revisions.
The proposed license extensions are within the original design considerations for the station and the current surveillance, inspection, testing and maintenance practices provide assurance that degradation in plant equipment will be identified and corrected throughout the lifetime of the facility.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated since no changes are required to the design or operation of the station.
3.
The proposed amendment does not involve a significant reduction in a margin of safety since no changes are required to the design or operation of the station and since the amendment does not involve new or revised safety analyses, procedure changes, UFSAR revisions or Technical Specification revisions.
The current surveillance, inspection, testing and maintenance practices provide assurance that degradation in plant equipment will be identified and corrected throughout the lifetime of the facility.
Based on the above considerations, we contend that the extension of North Anna's operating licenses in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of accidents previously considered, nor create the possibility of a new or different kind of accident and will not involve a significant reduction in a safety margin.
Therefore, we conclude that there is no significant hazards consideration associated with the proposed revision to North Anna operating licenses.
61-WBR-96678-9 l
VIII. CONCLUSIONS Based.on the evaluations presented above, an operating license amendment to provide for 40 years of operation does not involve an unreviewed safety question or a significant hazards consideration, and is-reasonable and consistent with the (1) original design considerations, (2) previous environmental assessments, (3) current maintenance, surveillance and inspection programs and (4) NRC regulations and policy.
4 61-WBR-96678-10